ML20082M235

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Semiannual Radioactive Effluent Release Rept,Jan-June 1991
ML20082M235
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 06/30/1991
From:
DETROIT EDISON CO.
To:
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ML20082M224 List:
References
NUDOCS 9109050097
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DETROIT EDISON COMPANY FERMI 2 NUCLEAR POWER PLANT OPERATING LICENSE NO. NPF - 43 SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT for the period of January-1,-1991 through June 30,1991 i

9109050097 910830 PDR ADOCK 05000341 R POR

. i Effluent Reloase Report  !

August 1991 i TABLE OF CONTENTS L

I PAGE f

Preface i l l

1. Introduction 1  ;

I

2. Regulatory Limits 1
3. Maximum Permissibla Concentration 3
4. Average Energy 3  ;
5. Measurements and Approximations of Total Activity 4  :
6. Abnormal Releases 8  !
7. Batch Releases 8
8. Liquid Effluent Summary 9  :

i Oaseous Effluent Summary

9. 11
10. Solid Waste and Irradiated Fuel Shipments 14 11, Radiation instrumentation 15 f

f '

12. Changes to the Process Control Program (PCP) 15
13. Changes to Dose Calcalation and Environmental 15 Monitoring Locations ,

~

14. Changes to the Offs!te Dose Calculation Manual (ODCM) 15
15. Major Changes to Radioactive Waste Systems 15
16. Liquid Holdup Tanks Exceeding Limits 15  ;

I l .

?

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i Fermi 2 Semlannual Radioactive Effluent Release Report  :

January 1,1991 through June 30,1991  !

t PREFACE  ;

i The purpose of the Fermi 2 Nuclear Power Plant is to provide safe, economic and reliable .

electrical energy to the people of Southeastern Michigan. In 1990. Fermi 2 generated over  !

7 million Megawatt-hours (net) of electricity, which is 15% of the total electricity generated by the Detroit Edison Company in 1990.

r Fermi 2 is designed, constructed and operated in accordance with the standards and t requirements established by the U.S. Nuclear Regulatory Commission (USNRC) to ensure [

that any potential radiation doses to members of the public will be "as low as reasonably achievable' (ALARA). f The USNRC defines the term "as low as reasonably achievable" to mean *as low as t reasonably achievable taking into account the state of technology, and the economics of l improvements in relation to benefits to the public health and safety, and other societal and Socioeconomic considerations, and in relation to the utilization of atomic energy in the public interest".  ;

l The Semlannual Effluent Release Report contains data and information regarding  ;

radioactivity which was released in gaseous and liquid effluents and a's solid radloactive  ;

waste from the Fermi 2 Nuclear Power Plant from January 1,1991 through June 30,1991, i This preface includes a perspective on radioactive effluent releases and annual radiation t dosos to members of the public which are calculated from the radloactive effluent release -!

data, covering the entire period of Fermi 2 operation (1985-1991).

The radiation doso data which are contained in this report are calculated by using [

conservativo methods and models, which are required and approved by the USNRC. This t ensures that any assessment of compliance with USNRC standards and requirements will be based upon calculated values which represent the maximum potential radiation doses to ,

members of the public. Actual radiation doses to a member of the public from Fermi 2  ;

radioactive effluents may be much less than the calculated values in this report, ,

Figure I shows that over the six years that Fermi 2 has operated, no member of the public  !

has received annual radiation doses exceeding 2/10ths of one millirem (0.2 millirem) to the total body due to radioactive effluents from the plant. [

Table 1 shows that the highest calculated annual total body exposures from noble gas and liquid radioactive effluents (in 1989) are each less than 2% of the limitt, approved by the USNRC in the Fermi 2 Technical Specifications. For all other years of Fermi 2 operation, each of the calculated annual total body exposures from radioactive gaseous and liquid effluents are less than 1% of the limits.

The calculated radiation exposure from radioactive noble gases shown in Table 1 for 1989 {

is approximately throo times the value for 1990. The difference in the calculated radiation exposure values is due to a revision made in 1990 to the calculation method to more ,

accurately reflect the actual release characteristics. The calculated radiation exposure value for 1990 (0.046 millirad) is conservative, but 't is more realistic than the value ,

calculated in 1989 (0.136 millirad) using the original calculation method. '

i i

i  !

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' Figure 2a shows the quantitles of radioactivity which were released annually in radioactive gaseous effluents from Fermi 2. Most (99%) of the radioactive gaseous effluents consist of short-lived noble gases which decay away in minutes or hours lhe noble gases are inert, which means that they do not concentrate in the environment or in the human body. The increase in gaseous radioactive effluents after 1988, when compared to the data for 1985-1988, is due to the fact that the plant first achieved full power commercial operation in 1988.

Figure 2b shows the annual wastewater volumes and radioactivity which were released in 1985-1991. The decrease in wastewater volumes released annually since 1985-1987 is due to improved plant operation and water management practices The bl0her wastewater volumes and radioactivity released in 1989 and 1991 compared to the lessor amounts released in 1990 are due to the increased usage and processing of water within plant systems during the first and second refueling outages in 1989 and 1991. There was no refueling outage in 1930.

The Natlur.at Council on Radiation Protection (NCRP) estimates that the average person in the U.S. receives approximately 300 millirems per year from sources of natural background radiation. Also, the NCRP estimates that an additional 60 millirems per year is received from sources of med! cal radiation exposure and from consumer products. By those NCPP estimates, the average person in the U S. receives approximately 360 millitems per year from ngtural and man made sources of radiation exposure, other than commercial nuclear power.

The NCRP estimate of 360 millirems per year is more than 1 k60 t'mes the maximum calculated annual radiation dose of tess than 2/10ths of ene Tulliram to the total body from Fermi 2 radioactive effluents, which occurred in 1989. The annual calculated radiation exposure from Fermi 2 radioactive effluents contributes less than 6/100ths of one per cent

(< 0.06%) of the average total body radiation exposure received per year by a member of the public frorn natural and other man-made sources of exposure.

I National Council on Radiation Protection and Measurements Report No. 93, 'lonizing Radiation Exposure of the Population of the United States', published in 1987, i

11

4 Effluent R: lease Report ,

Maximum C:lcul:ted Tot:l Body Dos 313 o Member August 1991  ;

. of the Putdic from Fermi 2 RaCoactive Altbome and Liquid Effluents 19115 - 1991 l u =  :

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ETotal Dose  !

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I Data Summary Table  !

Radiation Dose (milliroms)

Altbomo Liquid i Year Emuonts Effluents Total [

L 2.. a. 4" 4 1  !

1 9885 N.D. <0.001 <0.001 1986- N.D. 0.011 0.011 i f

1987 <0.001 0.001 0.001 h

1980 <0.001 0.004 0.004  !

f 1989 0.137 0.033 0.170 1990 0.046 0.005 0.051

  • 1991 0.015 0.016 0.031 [

N.D.= No radioactMty was detected. f I

  • Data for 1991 is for January - June 1991 only [

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Effluent Relosse Roport Au0ust 1991 Tablo 1 Comptrison of Formi 2 Calculated Radoactivo Ettluont Exposuro Dita (Total Body) to Fermi 2 Techn'cal Specifeation Annual Umlts Calculated Total Body Exposure Dueto Due to Noble Gas (mrad) Liquid Effluents (mrom)

Year Illmlt = 10 mrad'yr) (Limit = 3 mrom/yr)

L 1 1985 N.D. <0.001

(<0.01 %)

1986 N.D. 0.011 (0.37%)

1987 N.D. 0.001 (0.03%)

1988 <0.001 0.004

(<0.01%) (0.13%)

1909 0.136 0.033 (1.36%) (1,10%)

1990 0.046 0.005 (0.tS*".) (n 17%)

  • 1991 0.015 0.016 (0.15%) (0.53%)

N.D. n No radioactivo noble gases were detected.

  • Data for 1991 is for January - June 1991 only IV

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Effluent Release Report  !

.. August 1991 f

. Fermi 2 Radioactive Airborno Effluent Summary Data 1985 - 1991 l;

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F Data Summary Table  ;

Radioactivity Released (Curies) [

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t 1988 1,11 <0.001 0 002 1989 164 0.002 0.015 ,

i 1990 161 0.003 0.012  ;

  • 1991 25 4 0.001 0 001 '

i N.D. = No radioactivity was detected i

  • Data for 1991 is for January - June 199109ty f

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  • Effluent Release Repott August 1991 Fermi 2 Radioactivo Uquid Ettluent Summary Data 1985 - 1991 9 15 ry>

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l $syiPg37"d 19ss 1956 1937 1953 1939 iovo 1921 1933 1934 r 19, Year Year DVolume Discharged BRadioactivity Discharged Figuro 2b Data Summary Table voturne Dischar ged Radioactivity l Year _(Uter X 1000000) JCtrjes)_R 1905 S.33 0010 1986 7.01 0 304 1987 7.67 1.067 1900 1.09 1.007 1989 2 61 1472 iMO O B3 0 966 i 2 36 2.164

' Data tot 1991 is f(v January - June 1991 only vi

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  • Effluent Release Report

.. August 1991 .

Page 1 i

1. INTRODUCTION i The Detroit Edison Fermi 2 Nuclear Power Plant is designed and operated in a manner which strictly controls and monitors the release of radioactive effluents to the l environment in accordance with Nuclear Regulatory Commission (NRC) and Detroit  !

t Edison Company requirements. This Semlannual Radioactive Effluent Release Report is submitted in accordance with Fermi 2 Technical Specification 6.9.1.8 and NRC j Regulatory Guide 1.21. This report provides the following information required by j those references: i 4

1. Summation of the quantitles of radioactive material (in the form of gases and  !

liquids) released from the plant (Sections 8 and 9) .j q

2. Summation of quantitles of radioactive material contained in solid waste j packaged and shipped for off-site disposal (Section 10)
3. Charegos to the Process Control Program (PCP) (Section 12) )

i

4. Changes to the Offsite Dose Calculation Manual (ODCM)(Section 14) {

f

5. A list and description of any unplanned releases of radioactive materials to unrestricted areas (Section 6) {

i

6. A listing of any new locations for dose calculation or environmental i monitoring identified by the land use census (Section 13) f
7. A listing of effluent monitors which were Inoperable for a period longer than

.that specified in Technical Specifications 3.3.7.11 and 3.3.7.12, and an i explanation of why the time limit was exceeded (Section 11)  !

8. A description of events leading up to any liquid holdup tanks exceeding the I limit of Technical Specification 3.11.1.4 (Section 16) [

l

9. A description of any majur changes to radioactive waste treatment systems ,

t (Section 15)

This report covers the period of Jamary 1 through June 30,1991. ,

During the first half of 1991, the total gaseous and liquid radioactiva effluent releases 4 and resulting dose to the public were maintained As 1.ow As Reasonably Achievable [

(ALARA), in accura: :e with Fermi 2 Techalcal Specificatnon 6,9.1.8, the next . j Semlannual Radioactive Effluent Release Report--the one to be siibmitted within 60 1 days after January 1,1992--will contain dose assessments for all of 1991, t

,. 2. REGULATORY LIMITS i i- )

The Nuclear Regulatory Commission limits on liquid and gaseous offluents are  ;

incorporated in the Fermi 2 Technical Specifications. These limits prescribe the .

maximum quantitles and rates of release for radioactive affluents resulting from  !

normal operation of Fermi 2. The limits are defhed in several ways to limit the  ;

overall impact on persons living near the plant. The limits are described in the f followmg sections. [

3

-, . - _ . _ , . . . _' . . _ . _ . . . __ - . . . . - _ _ _ _. _ ..~. , , _

Effluent R: lease R: port August 1991 Page 2 r

A. Oaseous Effluents

1. Dose rate due to radioactive materials released in gaseous effluents from the I site to areas at and oeyonti the site boundary shall be limited to the following:
a. Noble gases f

Less than or equal to 500 mrem / year to the total oody less than or equal to 3000 mrom/ year to the skin

b. lodine 131,133, tritlutn, and for all radionucl! des in particulate form with half lives greater than 8 days '

, Ler,s than or equal to 1500 mrom/ year to any organ.

2. Air dose due to noble gases released in gaseous effluerns from the reactor to areas at and beyond the site boundary shall be limited to the following:
a. I.ess than or equal to 5 mrads for gamma radiation Less than or equal to 10 mrada for beta radiation

-During any calendar quarter

b. Less than or equal to 10 mrads for gamrna radiation Less than or equal to 20 mrads for beta radiation  ;

-During any calendar year

3. Dose to a member of the public from lodine-131,133, tritium, and all radionuct' des in palticulate form with half lives greater than 8 days in gaseous effluents released from the reactor to areas at end beyond the site boundary shall be limited to the following:
a. Less than or equal to 7.5 mrems to any organ

-During any calendar quarter c

b. Less than or equal to 15 mrems to any organ

-During any calendar year B. Liquid Effluents

1. The concdntration of radioactive material released in liquid affluents to unrestricted areas shall be limited to the concentrations specified in Title 10 of the Code of Federal Regulations Part 20 (Standards for Protection Against Radiation), Appendix 0 Table 11, Column 2 for radionuc!! des other than 4

dissolved or entrained noble gases. For dissolved or entrained noble gases,

- the contentration shall be limited to 2E-4 (.0002) rnicrocuries/ml total activity,
2. The dose or dose commitment to a member of the public from radioactive 4- materials in liquid effluents released from the reactor to unrestricted areas shall be limitert to the values in the following sections.

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Efflu:nt Rst:ase Report August 1991 Page 3 I

a. Less than or equal to 1.5 mrem to the total body Less than or equal to 5 mrem to any organ

-During any calender quarter

b. Less than or equal to 3 mrom to the total body Less than or equal to 10 rnrem to any organ

-During any calender year

3. MAXIMUM PERMISSIBLE CONCENTRATION (MPC)

Fermi 2 Technical Specifications implement the MPC requirements of 10 CFR 20 and NRC Regulatory Guide 1.21 by means of the following dose rate limits:

A. Gases The dose rate due to gaseous effluents is calculated in accordance with the Formi 2 Offsite Dose Calculation Manual (ODCM), The maximum permissible dose rates for gaseous releases are defined in Fermi 2 Technical Specifications:

Technical Specification 3.11.2.1.a (Dose rate at the site boundary from noble gases):

-Less than or equal to 500 mrom/ year to the total body

-Loss than or equal to 3000 mrem / year to the skin Technical Specification 3.11.2.1.b (Dose rate at the site boundary from l-131, 1-133, and particulates with half lives greater than 8 days):

-Less than or equal to 1500 mrom/ year to any organ B. Liquids Allowable liquid release rates are calculated in accordance with the Fermi 2 Offr,te .

Dose Calculation Manual (ODCM). The maximum permissible concentration (MrC) for liquids used for these calculations are taken from 10 CFR 20. Appendix 0, Tame 11, Column 2. The most restrictive MPC is used in all cases. For dissolved and entrained gases the MPC of 2E-4 microcuries/ml is appfled. This MPC is based on the Xe-135 MPC in air (submersion dose) converted to an equivalent concentration in water as discussed in the International Commission on Radiological Protection (ICRP)

Publication 2.

I- 4. AVERAGE ENERGY 1

t i The calculated site boundary dose rates for Fermi 2 are based on Identification of l individual isotopes and on use of dose factors specific to each identified isotope or a highly conservative dose factor, Average energy values are not used in these

, calculations, and therefore need not be reported.

t l

Efflu nt R:10aso R port August 1991 Page 4

5. MEASUREMENTS AND APPROXIMATIONS OF TOTAL ACTIVITY As required by NRC Regulatory Guide 1.21, this section describes the methods used to measure the total redloactivity in effluent releases and to estimate the overall errors associated with these measurements. The effluent monitor!ng systems are described in Chapter 11.4 of the Fermi 2 Updated Final Safety Analysis Report (UFSAR).

A. Gaseous Effluents

1. Fission and Activation Gases Samples are obtained from each of the seven plant radiation monitors which continuously monitor the six ventilation exhaust points and from the Offgas Vent Pipe which carries the gland seal condenser exhaust, me hanical vacuum pump exhaust, and treated offgas streams. The Offgas Vent Pipo effluent is released through one of the six ventilation exhaust points (the reactor building exhaust plenum). The fission and activation gases are quantified by gamma spectroscopy analysis of periodic samples.

The values reported in Section 9 are the sums of all fission and activation gases quantifled at all monitorod releaso points.

Considering the inherent variability in radiation measurement, the variability in effluent stream composition, and the uncertainties ;n effluent flow rate and instrument calibration, Detroit Edison estimates that the uncertainty of the fission and activation gas total release figures is less than plus or minus 8 percent.

2. Radiolodines Samples are obtained from each of the seven plant radiation monitors, which continuously monitor the six ventilation exhaust points. The radiolodines are entrained on charcoal and then quantified by gamma spectroscopy analysis.

For each sample the duration of sampIlng and continuous flow rate through the charcoal are used in determining the concentration of radiolodines. From the flow rate of the ventilation system a rate of release can be determined.

The values reported in Section 9 are the sums of all radiolodines quantified at all continuously monitored release points.

Considering the inherent variability in radiation measurements, the variability in effluent stream composition, and the uncertainty in sample and effluent flow rates, Detroit Edison estimates that the uncertainty of the total radiolodine release figures is less than plus or minus 5 percent.

. August 1991 Page 5 l i l

3. Particulates  !

t Samples are obtained from each of the seven plant effluent radiation monitors, I which continuously monitor the six ventilation exhaust points. The paniculates are collected on a filter and then quantified by gamma spectroscopy analysis.

For each sample the duration of sampling and continuous flow rate through  ;

the filter bre used in determining the concentration of particulatas. From the l flow rate of the ventilation system a rate of release can be determined. l A composite of the filters from each ventilation release point is analyzed monthly for gross alpha radioactivity using gas proportional counting methods. Quarterly the filters are radlochemically separated and analyzed for i Struntium (Sr)-89/90 using various analytical methods, if found these  !

radionuclides are reported as total particulate activity.

The values reported in Section 9 are the sums of aP particulates quantified at all monitored release points.  ;

Considering the Inherent verlat:llity '.n redletion measurements, the verlability in .

effluent stream composition, and the uncertaintles in instrument calibretion [

and in sample and effluent flow rates, Detroit Edison estimates that the the i

l uncertainty of the total particulate release figures is less than plus or r:Inus 3  !

percent.  ;

4. Tritium Samples are obtained for each of the seven plant affluent radiation monitors [

which continuously monitor the six ventilation exhaust points. The sample is  ;

passed through a bottic containing water and the tritlum is

  • washed" out to i the collecting water. Portions of the collecting water are analyzed for tritium L using liquid scl"tillation counting techniques. For each sample, the duration of sample and sajple flow rate is used to determine the concentration. From the flow rate of the ventilation system a release rate can be determined.

The values repoded in Section 9 are the sums of all tritium quantified at all monitored relet, .e points.

Considering the inherent varlability in radiation measurement, the variability in effluent stream composition, and the uncertainties in instrument calibration, sample and effluent flow rates, and collection efficiency, Detroit Edison estimates that the uncertainty of total gaseous tritium release figures is less I than plus or minus 34 percent.

Efflu:nt R:l:aso Report August 1991 '

Page 6

5. Gross Alpha The gaseous particulate filters from the seven plant effluent radiation monitors are stored for one week to allow for decay of naturally occurring alpha emitters. These filters are then analyzed for gross alpha radioactivity by gas proportional counting, and any such radioactivity found is assumed to be plant related. The quantity of alpha emitters released can then be determined from sample flow rate, sample duration, and stack flow rate.

The values reported in Section 9 are the sums of all alpha emitters quantitled at all monitored release points.

Considering the inherent verlability in radiation measurements, the variability in effluent stroam composition, and the uncertainties in instrument calibration and in sample and effluent flow rates, Detroit Edison estimates that the .

uncertainty of the total gaseous gross alpha release figures is less than plus or minds 10 percent.

D. l.lquid Effluents The liquid radweste processing system e ad the liquid effluent monitoring system are described in the Ferml-2 8SAR.

1. Fission and activation products Before the contents of each holding tank is discharged to the environment, a representative sample of the tank's contents is taken and retained. The sample allows for the determination of radioactive material concentrht:ons and I establishes the rate at which the radioactive material can be discharged to the i environment.

At the end of the calendar quarter a composite sample is made of all discharge samples taken during the quarter. This composite r. ample consists of portions of each discharge sample which are proportional to the volumes 1 discharged. The composite sample is analyzed for Iron (Fe)-55 and Strontium l (Sr)-89/90. Radiochemical separations and various analytical methods are used to quantify the amounts of Sr-89/90 and Fe-55.

The values reoorted in Section 8 are the sums of all fission and activation products found in all batch releases.

Considering the inherent variability in radiation measurement and the uncertainties in volume measurements and instrument calibration, Detroit Edison estimates that the uncertainty in total liquid fission and activation product release figures is luss than plus or minus 5 percent.

l 1

. Effluent Release R:p;rt August 1991 Page 7 l ..

2. Tritium ,

Before the contents of each holdit.g tank is discharged to the environment, a i representative semple of the tank contents is taken and retained. At the end  ;

of the calendar month a composite sample is made of all discharge samples taken during the month. This composite sample contists of portions of each discharge sample which are proportional to the volumes discharged. The

composite sample is analyzed for tritlum by liquid scintillation counting.

l The values reported in Section 8 sums all tritium quantified from all batch releases.

Conaldering the inherent variability in radiation measurement and the ,

uncertainties in volume measurement and instrument calibration, Detroit Edison estimates the uncertainty in total tritium release figures is less than

  • plus or minus 15 percent.

I  ;

I 3. Dissolved and Entrained Oases Prior to releasing liquid radioactive waste to the environment a sample la taken from the radwestt lolding tank. This sample is representative of the ,

tank's contents. The sarnple is examined using gamma spectroscopy to l determine the dissolved and entrained noble gases, ,

i The values reported in Section 8 are the sums of all radioactive gases found l for all batch releases.

Considering the inherent variability in radiation measurement and the ,

uncertaintles in instrument calibration and volume measurements, Detroit l Edison estimates that the uncertainty in total dissolved and entrained gas '

release figures is less than plus or minus 15 percent.

4. Gross Alpha Before the contents of eech holding tank is discharged to the environment, a representative sample of the tank's contents is taken and retained. At the end of the calendar month a composite sample is made of all discharge samples taken during the month. This composite sample consists of portions of each discharge sample which are proportional to the volumes discharged. The composite sample is analyzed for gross alpha radioactivity by gas proportional counting.

l The values reported in Section 8 are the sums of the gross alpha radioactivity l from all batch releases.

i Considering the inherent variability in radiation measurement and the i

uncertainty in volume measurements and instrument calibration, Detroit Edison i-l estimates that the uncertainty in total liquid gross alpha release figures is less than plus or minus 43 percent.

k

f.* - Efflu:nt R:leaso R: port l

August 1991 Page 8

6. ABNORMAL RELEASES 1

For the purpose of this report, an abnormal release is any release of radioactive material not performed in accordance with the Fermi 2 license and implementing procedures. No abnormal releases occurred during the reporting period,  !

l

7. BATCH RELEASES As required by Regulatory Guide 1.21, a summary of data for batch releases is provided below. The following batch liquid releases from raiwaste holding tanks to the Circulating Water Decant Line occurred between January 1,1991 and June 30, 1991:

Number of releases: 30- ,

Total time for all releases: 13,126 minutes  ;

Maximum time for a release: 490 minutes Average time for a release: 438 minutes Minimum time for a release: 380 minutes The only batch gaseous releases from Fermi 2 are the venting or purging of the  ;

primary containment (drywell) atmosphere. These venting or purging releases pass '

through the reactor building ventilation or standby gas treatment system and are monitt., red by the final effluent monitors for these pathways. Separate data on these venting or purging releases are not reported because the associated data are already included in the gaseous effluent release data (5,ection 5.A and Section 9).

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  • Effluent Release Repon August 1991 Page 9 l ,
8. LIQUID EFFLUENT

SUMMARY

REPORT CATEGORY SEMIANNUAL SUMMMATION OF ALL RELEASES OY QUARTER TYPE OF ACTIVITY ALL LIQUID EFFLUENTS REPORTING PERIOD QUARTER 1 AND QUARTER 2 TYPE OF EFFLUENT UNIT QUARTER 1 QUARTER 2 A, FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITlUM, GASES, ALPHA) CURIES 6.01 E-02 1.46E-01
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCl/ml 6 87E-09 181 E-08 _
3. MAXIMUM PERCENT OF TECHNICAL SPECIFICATION LIMIT FOR A SINGLE RELEASE  % 8 79E-01 7 03E-01 B. TRITIUM
1. TOTAL RELEASE CURIES 6 98E-01 1.2 6 E + 00
2. AVERAGE DILUTED CONCENTRATION DURING PER!OD uCl/ml 7 980-08 1.56E-07
3. PERCENT OF TECHNICAL SP,ECIFICATION LIMIT  % 054E-02
  • 6 58E-02 C. DISSOLVED AND EN_T, RAINED GASES
1. TOTAL RELEASE CURIES 6.82E-05 1.83E-06
2. AVERAGE DILUTED CONCENTRATION DURING PERIOD uCl/mi 7.79E-12 2.2 7 E- 13
3. PERCENT OF TECHNICAL SPECIFICATION UMIT  % 1.40E-04 143E-06 D. GROSS ALPHA RADIOACTIVITY (Note: N.D. = No activity detected)
1. TOTAL RELEASE CURIES N D. N.D.

E. WASTE VOL RELEASED (PRE-DILUTION) LITERS 6.46E+05 1.71 E +06 F. TOTAL VOLUME DILUTION DISCHARGED LITERS 8.7 5 E + 09 8 07E+09

Effluent R:l: ass Report '

, Au0ust 1991

,, Pa0s 10

8. L10Ul0 EFFLUENT

SUMMARY

(continued)

REPORT CATEGORY  : SEMIANNUAL LIQUID DATCH RELEASES  ;

TYPE OF ACTIVITY  : TOTALS FOR EACH NUCLIDE RELEASED l

' ALL RADIONUCLIDES -

REPORTINO PERIOD QUARTER I AND OUARTER 2 DATCH RELEASES  !

. UNIT  : OUARTER 1 . QUARTER 2 NUCLIDE *

1 ALL NUCiiDES t H-3 CURIES 6,98E-01 1.26 E + 00 I Na-24  : CURIES .655E-03 1.52E-03 Cr-51 CURIES . 3.14E-02 9.16E-C2 Mn-54 CURIES 2.44 E-03 . 8.88E-03 I Co-58 CURIES . 3 20E-03 . 7.01E-03 Co-60 CURIES 3.85E-03 1.05E-02 Zn-65 CURIES . 2 50E-03  : 5.695-03 i Fo-59 . CURIES  ;* < 5.2E-08  : 4.48E-04 i' Tc 99m ' CURIES 1.86E-03 .0.79E-04 l-131 CURIES 1.03E-04  :* < 2.7 E-08 i 1-133 CURIES
  • 2.08E-04  :* < 1.8E-08 f Xe-133
  • CURIES 1.34E-05  :* < 7.3E-08 i Xe-135
  • CURIES ' 5.48E-05  : 1.83E-06 '

Sr-89 . CURIES .1.29E-04 . 9.92E-05 Sr-90 CURIES  :* < 7.0E-09  :* < 5 0E-09 ,

Fe-55

  • CURIES 7.11 E-03 .1.88E-02  ;

Ba-131  : CURIES * < 6.8E-08  : 1.04E-04 3 Ba-133m CURIES  ;* < 9.9E-08  : 2.50E-05  !

Ru-103 CURIES ** < 2.3 E-08 1.58E-05 i Ag-110m CURIES  ;* < 1.5E-07 . 7.10E-06 i As-76 CURlES 5 45E-04 1.02 E-03 Re-188 CURIES . 1.37E-04  :* < 1.3E-07 Ni-65 CURIES 627E-05 * < 2.1 E-0 7 Cs-134 . CURIES * < 2.5E-08  :* < 2.5E-08  !

Cs-137 . CURIES '* < 3.1 E-08 * < 31 E-08 i Co-141 CURIES * < 2.8E-08  :* < 2 8E-08  :

Co-144 CURIES * < 1.5 E-07 * * < 1.5 E-0 7 f Total for Period CURIES 7.58E-01 1.41 E + 00 Less than Lower Limit of Detection (LLD). i e. the maximum sensitivity of measurement, in units ,

of microcuries por mililliter (uCl/ml).

i f

Efflu:nt Rel:aso Report August 1991 Page 11 ,

. e r

9. GASEOUS EFFLUENT

SUMMARY

e f

REPORT CATEGORY . SEMIANNUAL SUMMMATION OF ALL RELEASES BY QUARTER l TYPE OF ACTIVITY , ALL AIRBORNE EFFLUENTS REPORTING PERIOD  : QUARTER 1 AND QUARTER 2 t t

UNIT  : QUARTER 1  : OUARTER 2 TYPE OF EFFLUENT  :

i A. FISSION AND ACTIV,ATION GASES , i i

1. TOTAL RELEASE _
CURIES 2.20E + 01 3.42 E+ 00
2. AVERAGE RELEASE RATE FOR PERIOD uCl/sec 2.83 E +00 4.35E-01 >

B, RADIOIODINES

1. TOTAL IODINE - 131 CURIES  : 7.00E-04 2.32 E-0 4  ;
2. AVERAGE RELEASE RATE FOR PERIOD uCl/sec 9.00E-05 2.95E-05 l i

i C. PARTICULATES l t

1. PARTICULATES i (HALF-LIVES >8 DAYS)  : CURIES 7.59E-04 3.52E-04
2. AVERAGE RELEASE RATE FOR PERIOD uCl/sec 9.76E-05 4.48E-05 r 1
3. OROSS ALPHA RADIOACTIVITY  : CURIES 4.50E-07 1.47 E-06 [

t D. TRITIUM (Note: N.D.

  • No activity detected) l
1. TOTAL RELFASE CURIES N.D. N.D.

_ l

2. AVERAGE RELEASE RATE FOR PERIOD j uCl/sec ,

N.A. N.A.

1 I

\_

\

f t

t

Efflusnt Rel:aso R: port August 1991 Page 12

3. GASEOUS EFFLU N

SUMMARY

(continued)

REPOM CATEGORY  : SEMIANNUAL AIRBORNE CONTINUOUS RELEASES TYPE Of ACllVITY  : FISSION GASES, IODINES, AND PARTICULATES 3EPORTING PERIOD :QU ARTER 1 AND QUARTER 2

MIXED MODE RELEASES
UNIT OUARTER1  : QUARTER 2 NUCLIDE - -

PARTICULATES Cr- 51 . CURIES 3.07E-04 5.78E-05 Mn-54 CURIES .1.08E-05  : 6.97E-05 Fe-59  : CURIES * < 1.8E-13 . 3.49E-05 Co-58  : CURIES . 5.42E-06  : 1.65E-05 Co-E>0 , CURIES . 2.14E-05  : 9.98E-05 Na-24 . CURIES . 7.07E-04 9.66E-05 l

Zn-65  : CURIES  : 4.87E-06  : 3.18E-05 Tc-99m CURIES 2.36E-03 3.87E-05 Ba-139  : CURIES , 3.23 E-01  : 4.37E-02 Ba-140 CURIES - 3.19E-04 . 1.91 E-05 La-140  : CURIES  : 2.15E-04  : 6.83E-05 Y-91m CURIES 1.92 E-03 1.47 E-04 Sr-91 CURIES 3.06E-03  : 2.78E-04 Rb-89 CURIES 3.65E-01 4.86E-02 Cs-138  : CURIES 1.72E-01 , 2.03E-02 Re-188 CURIES , 7.32E-05  :* < 9.8E- 14 Br-82 . CURIES 1.47E-05  :* < 5.1 E- 14 Se-75 CURIES  ;* < 2.5E- 14  : 8.00E-06 Rb-88  : CURIES  : 2.33E-04  :* < 2.3 E- 1 1 Sr-89 . CURIES 8.97 E-05 , 1.36 E-05 S.-90 CURIES 4.89E-07 3.26 E-07 Cs-134 CURIES * < 3.6E- 14  ;* < 3.6E- 14 Cs-137  : CURIES * < 4.7 E- 14 * < 4.7E- 14 l

Ce-141  : CURIES * < ? "i-14 * * < 3.1 E- 14 Co-144 CURIES *< i-10 * < 1.2 E- 13 l

Total for Period  : CURIES 8.69E-01 1.14E-01 l

l Less then the Lower Limit of Detection (LLD), i.e. the maximum sensitivity of measurement in units of microcuries per milliliter (uCl/ml) 1.

i l

Efflu:nt Rel: ass R: port.

August 1991 Pags 13 l -.

- 9, GASEOUS EFFLUENT

SUMMARY

(continued)

REPORT CATEGORY  : SEMIANNUAL AIRBORNE CONTINUOUS RELEASES TYPE OF ACTIVITY FISSION GASES. IODINES, AND PARTICULATES REPORTING PERIOD  : QUARTER 1 AND OUARTEH 2

MIXED MODE RELEASES
. UNIT OUARTER 1  : QUARTER 2 NUCLIDE -

FISSION GASES _

Ar-41 . CURIES

  • 2.20E+00 . 1.37 E + 00 l Xe-135m
  • CURIES 1.25E + 00 1.06E-01 Xe-138 CURIES  : 2.71E+00 3.46E-01 Xe-135 . CURIES C04E-01 * < 2.7 E-08 Kr-85m CURIES , 1.77 E + 00 2.97E-01 Xe-137 CURIES :817E+00-
  • 1.09E+00 Kr- 88 . Cl; RIES  : 1.72E+00 . 2.10E-01 Kr-89 . CURIES  : 3.54E+00  :* < 2.0 E -06 Xe-133  : LURIES . 3.93E-01 * < 4.1 E-08 Total for Period CURIES 2.20E +01 3.42E+00 IODINES ,

1-131 CURIES 7.00E-04 . 2.32E-04  !

1-132 CURIES 6.28E-04 1.42E-04  :

1-133  : CURIES . 3.64E-03 7.38E-04 1-134 . CURIES

  • 2.91E-04 * < 1.6 E- 13 1-135 CURIES 1.17E-03 7.46E-04 [

Total for Period CURIES 6.43ti-03 1.86E-03 Less than the Lowr- Lim.6 of Detection (LLD), i.e. the maximum sensitivity of measurement in units of microct les per milliliter (uCi/ml) [

i

[

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Effluent Release Report August 1991 Page 14 10.

SOLID WASTE AND IRRADIATED ENTS FUEL SHIPM A.

Solid Waste Shipped Offsite for burial or di 1.

sposal (not irrad!ated fuel)

Type of Waste Unit 6 month period Est. Total

a. Spent resins, filter sludges, Error %

evaporator bottoms, etc. m3 0 00E+00

b. Curles NA Dry compressible wastes, 0.00E+00 NA contaminated equipment, etc. m 2.16E +01 Curies 125
c. Irradiated components, 2.02E+00 control rods, etc. 125 1
d. Other O NA 0

l

2. NA Estimate of major nuclide composition (b Dry active waste: y type of waste)

Nuclide Percent of Total Activity Mn-54 Curies Fe-55 5.6 Co-60 81.0 1.13E-01 Zn-65 8.5 1,64E+00 C-14 46 1.73E-01 Tc-99 0.2 9.28E-02 1-129 < 0.1 4.2/E-03 H-3 < 0.1 2.35E-04 N.A. 1.56E-04 Note:

Not detected Activities of all principal radionuclid

3. es were determined by measurement.

Solid Waste Disposition (All waste was Cl Type of shipment / ass A and was shipped in LSA containers) .

solidification process Number of shipments Mode of Dry active waste Transport 1

Destination truck Chem-Nuclear Systems, Inc.

4. Channahon, IL Irradiated Fuel Shipments:

None

.. - . _. __ . _ _ - _ . . . _ - . _ . . - - . ~ . _ . _ . - _ .

_ .. __-_m_. ..

i. Efflusnt Rsi aso Report =

g,3 ' August-1991 Pago 14 -

! 10, SOLID WASTE AND IRRADIAI.2D FUEL SHIPMENTS j" _

Ai . Solid Waste Shipped Offsite for burial or disposal (not irradiated fuel) 6 month Est, Total

1. Type of Waste - Unit - period Error %
a. Spent resins, filter sludges, m3 0.00E+00 - NA evaporator bottoms, etc. Curites 0.00E+00 NA
b. Dry _ compressible waste, m 2.16E+01 +25 contaminated equipment, etc. Curles 2.02 E+ 00 +25 ,
c. -Irradiated components, control rods, etc. O NA t
d. Other 0 NA
2. Estimate of major nuclide composition (by type of waste)

Dry act;,e waste:

Percent of Nuclide Total Activity Curles

._Mn-54 5.6 1.13E-01 Fe '5 81.0 1.64E+00 Co-60 85 .

1.73E-01 Zn-65 4.6 9.28E-02 C-14 0.2 4.27E-03 Tc-99 < 0,1 2.35E-04 l-129 < 0.1 1.56E-04 -

H-3 N.A. Not detected Note:- Activities of all principal radionuclides were determined by measurement.

3. Solid Waste Disposition (All waste was Class A and was shipped m LSA_ containers.)

Type of shipment / Number of Mode of

- solidification process shipments - Transport Destination Dry active waste 1 truck Chem-Nuclear

, Systems, Inc.

Channahon, IL

4. Irradiated Fuel Shipments:

None

_ ~ , _ ._ . _ . . -___ _ .

M. Efflu:nt Rel:ase R: port O

. August 1991

,,. Paga 15

11. RADIATION INSTRUMENTATION Fermi 2 Technical Specifications 3.3.7.11, Radioactive Liquid Effluent Monitoring Instrumentation, and 3.3.7.12, Radioactive Gaseous Effluent Monitoring instrumentation, require that those monitors which exceed the time specified for out of service be reported in the next Semlannual Effluent Release Report. During this ,

reporting period, January through June of 1991, the time specified in the action '

statements for these monitors was not exceeded. ,

12. CHANGES TO THE PROCESS CONTROL PROGRAM (PCP)

As required by the Fermi 2 license the operatur (Detroit Edison) is required to establish a program that will reasonably assure tne complete processing of radioactive wastes. This program assures processed wastes are completely solidified and are free of standing water. Changes to the PCP Manual are provided to document changes to established conditions and to ensure that controls are in place to assure that the radloactive waste is solidified.

During this reporting period, Jenuary through .une of 1991, there were no changes to the PCP.

13. CHANGES TO DOSE CALCULATION AND ENVIRONMENTAL MONITORINO LOCATIONS in June,1991, a new milk sampling location (the Roelant farm, M-4) was added.

However, after 3 scheduled samples were obtained, the milk animal was sold. This location has been dropped as a milk sample location but is retained as a vegetation >

sample location.

14. CHANGES TO THE OFFSITE DOSE CALCULATION MANUAL (ODCM) I E

During this reporting period, January through June of 1991, there were no changes to the ODCM.

15. MAJOR CHANGES TO RADIOACTIVE WASTE SYSTEMS During this reporting period, January through June of 1991, there were no major .

changes to the liquid, gaseous or solid radioactive waste treatment systems.

i

16. LIQUID HOLDUP TANKS EXCEEDING LIMITS l- Fermi 2 Technical Speculcation 3.11.1.4 requires that the quantity of radioactive l matcrial contained in any outside temporary tank shall be limited to 10 curies, excluCing tritium and dissolved or entrained noble gases. During this reporting period, January through June of 1991, this activity limit for such tanks was not exceeded.

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